IR 05000244/2021010
| ML21155A020 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/07/2021 |
| From: | Glenn Dentel Division of Operating Reactors |
| To: | Rhoades D Exelon Generation Co |
| References | |
| IR 2021010 | |
| Download: ML21155A020 (8) | |
Text
June 7, 2021
SUBJECT:
R.E. GINNA NUCLEAR POWER PLANT, LLC - NRC INSPECTION REPORT 05000244/2021010
Dear Mr. Rhoades:
On May 20, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at R.E. Ginna Nuclear Power Plant, LLC and discussed the results of this inspection with Mr. Paul Swift, Site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket No. 05000244 License No. DPR-18
Enclosure:
As stated
Inspection Report
Docket Number:
05000244
License Number:
Report Number:
Enterprise Identifier: I-2021-010-0014
Licensee:
Exelon Nuclear
Facility:
R.E. Ginna Nuclear Power Plant, LLC
Location:
Ontario, New York
Inspection Dates:
May 03, 2021 to May 20, 2021
Inspectors:
M. Patel, Senior Reactor Inspector
C. Hobbs, Reactor Inspector
B. Pinson, Reactor Inspector
Approved By:
Glenn T. Dentel, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an NRC inspection at R.E. Ginna Nuclear Power Plant, LLC, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
However, all the inspection activities were performed onsite.
REACTOR SAFETY
===71111.21N.05 - Fire Protection Team Inspection (FPTI)
Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)===
The inspectors verified that components and/or systems will function as required to support the credited functions stated for each sample. Additional inspection considerations are located in the fire hazards analysis (FHA) or safe shutdown analysis (SSA).
- (1) Fire Protection Water Supply System - Fire Pumps and Tank
- (2) Chemical and Volume Control System, including Alternate RCS Injection System
- (3) Standby Auxiliary Feedwater System
- (4) Fire Penetration Seals
Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)
The inspectors verified that the selected control or process is implemented in accordance with the licensees current licensing basis. If applicable, ensure that the licensees FPP contains adequate procedures to implement the selected administrative control. Verify that the selected administrative control meets the requirements of all committed industry standards.
- (1) Combustible Control Program
- (2) Fire Brigade Training, Drills, and Qualifications
Fire Protection Program Changes/Modifications (IP Section 03.03) (1 Sample)
The inspectors verified the following changes to the approved fire protection program do not constitute an adverse effect on the ability to safely shutdown.
- (1) ECP-19-000271-209-01-01, Replace S26 Alarm Check Valve and Install new electronic time delay vs. retard chamber to prevent inadvertent fire pump starts
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 20, 2021, the inspectors presented the NRC inspection results to Mr. Paul Swift, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.05 Corrective Action
Documents
259521,
277334,
287990,
4319723,
26202,
4366987,
4385406,
4388167,
4391803,
4404734,
4406238,
4416369
Corrective Action
Documents
Resulting from
Inspection
24323,
24527,
21635,
24750, PCR
21-01606
Drawings
33013-1230
Alternate RCS Injection System (BDB) P&ID
Revision 7
33013-1238
Standby Auxiliary Feedwater (FW) P&ID
Revision 44
33013-1265
Auxiliary Control Building Chemical Volume Control
System Charging (CVCS), Sheet 2
Revision 27
33013-3131
SAFW and NFPA805 1000KW STANDBY DIESEL
GENERATOR SETS
Revision 3
Engineering
Changes
ECP-12-000459,
ESR-11-0050
DDSAFW Project Electrical Design and Installation
Revision 1
ECP-14-000169
Alternate RCS Injection System
Revision 000
ECP-19-000271
Replace S26 Alarm Check Valve
Revision 001
ECP-21-000006
Extended Diesel Fire Pump Auto Start Test Frequency
from Weekly to Monthly
Revision 000
Miscellaneous
EPM-FPPR
R.E. Ginna Nuclear Power Plant Fire Protection Program
Revision 19
GINNA UFSAR
Revision 29
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
LR-FWS-
PROGPLAN
Fire Water System Program
Revision 9
Technical
Requirements
Manual for R.E.
Ginna Nuclear
Power Plant
Revision 73
Procedures
A-54.7
Fire Protection Tour
Revision 039
ATT-18.1
Alternate RCS Injection / Standby Aux
Revision 005
ER-FIRE.0
Control Response to Fire Alarms and Reports
Revision 18
ER-FIRE.1
1, Shift Technical Advisor (STA)
Revision 042
ER-FIRE.1
4, Control Operator (CO)
Revision 050
ER-FIRE.1
8, Long Term DC Power Supply
Revision 050
FPS-2
Ginna Station Fire Barrier Penetration Seal Program
Revision 9
FPS-3
Fire Barrier Inspection Program
Revision 5
FPS-7
Velocity Flush of the Fire Water System
completed
04/16/2018
FSG-4
ELAP DC Bus Load Shed / Management
Revision 003
Operator Response Time Program
Revision 7
OP-GI-102-106
Operator Response Time Program at Ginna Station
Revision 12
STP-O-40.10
Alternate RCS Injection System Flow Test (PCH02,
PDB07A, PDB07B)
completed
11/03/2020
STP-O-40.11
Alternate RCS Injection System Portable Diesel Run and
Pump Flow Test (PBD04)
completed
10/22/2020
Work Orders
C93709945,
C93710744,
C93719069,
C93720739